ML20154G855
| ML20154G855 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 03/04/1986 |
| From: | Daltroff S PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Butler W NRC, Office of Nuclear Reactor Regulation |
| References | |
| CON-#186-418 OL, NUDOCS 8603100129 | |
| Download: ML20154G855 (3) | |
Text
l PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET P.O. BOX 8699 PHILADELPHI A. PA.19101 12 51 848 5001 SHIELDS L. DALTROFF
.t.Eh'J"/.*o%E March 4, 1986 Docket No. 50-352 Mr. W.
R.
Butler, Chief License Branch No. 2 Division of Licensing U.S.
Nuclear Regulatory Commission Washington, D.C.
20555
SUBJECT:
Report of Change Being Made to the Limerick Generating Station, Unit 1 Initial Test Program
Dear Mr. Butler:
Condition No. 2.c(6) to the Limerick Generating Station License NPF-39 requires that changes made to the initial testing program described in the Final Safety Analysis Report be reported in accordance with the provisions of 10 CFR 50.59(b) within one month of such change.
The following Startup Test Program area has been changed:
o Test STP-25.3, MSIV Full Closure Testing, has been changed to test plant response durfn~g the closure of MSIV's at 90 to 100% power in lieu of the original testing requirements of 95 to 100% power.
On December 18, 1985 during a planned unit shutdown, a test window became available for conducting STP-25.3.
- However, the unit was at 91.7% power, rather than above 95% power as stipulated.
Analysis of the data taken during the transient indicates tha t testing at 91.7% is well within acceptable bounds of the predicted results because:
i e
gt 4
Performance of the plant and all protection systems is o
essentially the same at 100% power as that observed at 91.7% power.
8603100129 860304 PDR ADOCK 05000352 p
Mr.
W.
R.
Butler March 4, 1986 Page 2 o
The full power turbine trip (STP-27) which was more conservative and caused a more rapid shutoff of the main steam than the MSIV closure event was successfully performed during Test Condition 6, and resulted in a system response similar yet more conservative than test STP-25.3.
o Level 1 and Level 2 acceptance criteria for the MSIV (100% power) closure test were successfully demonstrated by the 91.7% power event.
o Operation of the MSIVs has been acceptably demonstrated previously during STP-25.1 and STP-25.2, MSIV functional testing.
Performance of an additional MSIV closure test at 95-100% power would provi..le only minimal additional information, since all of the objectives of test STP-25.3 were achieved successfully during the closure event conducted at 91.7% power.
This change does not involve an unreviewed safety question because it does not affect the evaluated design and does not affect any technical speci fication nor change any plant safety-related systems or equipment.
Should you have any questions or require additional information, please do not hesitate to contact us.
Very truly yours,
/
'I(C
/
cc:
Dr. Thomas E.
Murley, Administrator, Region I, USNRC E.
M.
Kelly, Senior Resident Site Inspector See Attached Service List
cc:
Troy B. Conner, Jr.,
Esq.
Ann P. Hodgdon, Esq.
Mr. Frank R.
Romano Mr. Robert L.
Anthony Ms. Phyllis Zitzer Charles W. Elliott, Esq.
Barry M. Hartman, Esq.
Mr. Thomas Gerusky Director, Penna. Emergency Management Agency Angus Love, Esq.
David Wersan, Esq.
Robert J. Sugarman, Esq.
Kathryn S.
Lewis, Esq.
Spence W. Perry, Esq.
Jay M. Gutierrez, Esq.
Atomic Safety & Licensing Appeal Board Atomic Safety & Licensing Board Panel Docket & Service Section (3 Copies)
E. M.
Kelly Timothy R. S. Campbell l
February 4, 1986
.